Preliminary data are enclosed in Tables I, II, II, IV, V, and VI. Tables I to V are data for round nickel tubes in a vertical and inclined (45°) position. Table VI contains some preliminary data for nickel rectangular channels (0.060" and 0.050" spacings) in a vertical position.

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This report summarizes results of measurements of density, viscosity, and surface tension of light and heavy water solutions of uranyl sulfate at elevated temperatures, which measurements were made at Mound Laboratory for the Homogeneous Reactor Project at Oak Ridge National Laboratory.

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It was demonstrated by differential thermal analysis (DTA) that: 1. Catastrophic amounts of energy can be stored in diamond. 2. Even at low irradiations, the release takes place over several hundred degrees, indicating a spectrum of activation energies. 3. At higher irradiations, the stored energy release is considerably less than the increased energy content and seems not to have been completely released even at the highest temperatures reached. 4. There is some indication of an increased heat capacity below the temperature of stored energy release. It was shown by DTA that large amounts of energy can be stored in silicon carbide on irradiation. The release was found to be spread out over a greater range of temperatures than in diamond and indicated a larger and higher group of activation energies. Catastrophic release was not achieved. The amount of stored energy released over the range of temperatures used was 140 cal/g in a sample irradiated in a water-cooled testhole at HEW for an exposure of 265 Mwd/aT. (auth)

It was demonstrated by differential thermal analysis (DTA) that: 1. Catastrophic amounts of energy can be stored in diamond. 2. Even at low irradiations, the release takes place over serval hundred degrees, indicating a spectrum of activation energies. 3. At higher irradiations, the stored energy release is considerably less than the increased energy contents and seems not to have been completely released even at the highest temperatures reached. 4. There is some indication of an increased heat capacity below the temperature of stored energy release. It was shown by DTA that large amounts of energy can be stored in silicon carbide on irradiation. The release was found to be spread out over a greater range of temperatures than in diamond and indicated a larger and higher group of activation energies. Catastrophic release was not achieved. The amount of stored energy released over the range of temperatures used was 140 cal/g in a sample irradiated in a water-cooled test hole at HEW for an exposure of 265 Mwd/aT.

An isothermal loop for testing a full-scale sodium pump for SRE and associated instruments has been operated for ~ 600 hrs. A summary of data obtained, together with recommendations, is given. (auth)

Abstract: "Probes were used to measure certain properties of the cloud of positive ions and electrons ejected from a pulsed ion source having two hydrogen-loaded electrodes. Time-of-flight measurements show: the presence of H+ ions with 50 ev directed energy; an increase of this energy with increasing pulse current in the source; a higher peak yield of ions with higher peak currents in the source; and higher yields and higher ion energies up to 110 ev have been recorded with the use of a pulsed magnetic field impressed upon the source. The neutral positive ion-electron beam from the source has been projected against an increasing magnetic field and the reflected and transmitted signals have been recorded and compared as a function of the magnetic field. Probe signals from the plasma as it encounters the magnetic field are oscillatory, suggesting that magnetohydrodynamic phenomena are presented."

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Reactivity calculations have been performed for the steady-state Pu feedback technique outlined in the previous progress report. A full-scale power plant study was initiated, based on sodium-graprite technology. A twin-core power plant is now considered to be the most promising configuration. Several design drawings are given of such a reactor, using slightly enriched U to produce Pu amd electrical power. The thermal neutron flux distribution in a cluster of 6 U rods was measured, and the results are compared with previous measurements for 7 rod cluster. The average thermal cycling of hollow U slug elements was begun. Results are given for 500 cycles between 100 and 500 deg C. A series of powder- compacted U alloys were thermal cycled between 200 and 700 deg C. Data on the transfur of radioactivity from Zr by Na has been obtained from a capsule of the first series of three miniharps. Fe, Al, and Cu were immersed in toluene end irradiated at 150 deg F in the MTR-Gamma canal. Toluene is being considered as a shield coolant for the SRE. The effect of 1-Mev electron irradlation on terphenyls was also studied. A venting tube arrangement has been designed for the Zr-canned graphite moderator. …

Technology of the Sodium Graphite Reactor. Reactivity calculations were made to study the application of steadystate plutonium feedback techniques to the use of diffusion plant tails for reactor fuel feed material. The performance and design of a twin core SGR power plant are given. Thermal neutron flux distribution measurements are reported for a six-rod fuel cluster and for a hollow uranium rod. A power cost calculation was made for a 1000-Mw SGR Th-U/sup 233/ breeder reactor which starts up on Th--U/sup 235/ alloy. Calculations were made on neutron leakage through the SRE shield. Research on reactor fuel elements and reactor materials are described. Corrosion and irradiation damage data at 5 x 10/sup 7/ r dose (150 deg F) on toluene as the SRE shield coolant indicate that the radioinduced corrosion of Fe, Al, and Cu in the SRE shield should be negligible. Preliminary results are summarized for l-Mev electron ir radiation studies of terphenyls at 400 to 450 deg C. Sodium Reactor Experiment. Progress is reported for various portions of the SRE project: reactor design and evaluation, fuel elements, moderator, reflector, structure, reactor cooling and heat transfer, instrumentation and control, shielding, and reactor services. (D.L.C.)

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The minimum shutdown time, to permit accessibility, for the Intermediate Power Reactor is estimated to be 38 hours. In case the reactor were shutdown following each rupture this long shutdown period would have serious disadvantages. The desirability of being able to make firm power commitments (independent of slug ruptures) has led to a study of the possibility of continuous operation following a rupture. There is evidence to indicate that, at the proposed water temperature, the rate of corrosion of uranium may be so high that at least a major portion of the rupture products may have entered the system before the reactor can be shutdown. A pushout of the affected column would then be a pushout of only those slugs which are still intact and the problem would still remain of removing the rupture products from the system. The first portion of this report is concerned with the rate of corrosion of a slug following rupture and the possible limitations to the principle of non-shutdown operation. These limitations include a flow stoppage by the ruptured can, undue increase in gamma activity, increased corrosion by the rupture products, and adherence of rupture products to the piping. The latter portion of the …

A design study has been made of a small "Package" nuclear power plant for the production of electric power and heat in remotely located, inaccessible areas devoid of natural fuels. The design utilizes a horizontal boiling reactor as a steam generator consistent with safe and simple equipment and a minimum building height. A reactor design of 51/2 Mw capacity, with a combined net electric power output of 750 kw and a heat plant output of 4500 kw, was studied in detail. Tertative cost estimates are presented on the basis of this combination. General comparisons have been made between different systems designed for either independent or combined production of 425 kw net electric power and 2500 kw available heat. (auth)

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Abstract: "In experimental studies, decontamination factors of 1000 to 3000 were obtained by electrostripping deposited radioactivity from stainless steel surfaces, used as the anode, in 2% sulfuric acid at current densities as low as 0.01 amp/in.-2. Stainless steel cathodes were used. The method was successfully applied to contaminated equipment."

Report presenting an experimental investigation to determine the pumping and thrust characteristics of four full-scale conical air ejectors over a range of primary gas temperature. The spacing ratio was found to influence both ejector pumping and thrust performance. Results regarding the ejector performance and ejector-shroud wall pressure distribution are also provided.

Abstract: This report is a brief description of a general purpose logarithmic counting rate meter developed at the Knolls Atomic Power Laboratory. The theory of operation and the circuit design are discussed. The use of a diode as a logarithmic element in the integrating circuit allows extremely accurate counting rate determinations over a five decade range.

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